ML20064B596
| ML20064B596 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 10/02/1990 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20064B597 | List: |
| References | |
| NUDOCS 9010180155 | |
| Download: ML20064B596 (18) | |
Text
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I 0,r UNITED STATES I
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,, #(f/j.g NUCLEAR REGULATORY COMMISSION, 5
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J ENTERGY OPERATIONS.'INC.
DOCKET NO. 50-382 l
WATEREORD STEAM ELECTRIC STATION. UNIT 3
-l AMENOMENT TO FACILITY OPERATING' LICENSE Amendment No. 63 i
License No. NPF-38 i
1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Entergy Operations, Inc.
t (thelicensee)datedJuly 25, 1990, complies with the-standards and requirements of the Atomic Energy Act'of 1954, as amended (the Act), and the Comission's rules and' regulations set forth in 10 CFR Chapter-I; B.
The facility will o perate.in conformity with' the application, r
the provisions of tie Act, and the rules and regulation' of the Commission; C.
Thereisreasonableassurance(1)thattheactivitiesLa'thorized u
by this amendment can be conducted without endangering the health
. and safety of the public, and (ii) that such activities will be i
conducted in compliance with the Comission's' regulations';'
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the.
public; and l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations ~.and all applicable 1
1 requirements have been satisfied.
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2 2.
Accordingly, the license is amended by changes to the Technical Specificetions as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No.
NPF-38 is hereby amended to read as follows.
(2) Technical Specifications and Environmental Protection Plan f
The Technical Specifications contained in Appendix A, as revised through Amendment No. 63, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the= license...
The licensee shall operate the. facility in accordance with the Technical Specifications and the Environmental Protection Plan, t
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATOR C0fiMISSION W
Theodore R. Quay, Acting' Director Project Directorate IV-1 Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation.
Attachment:
Changes to the Technical
-I Specifications Date of Issuance: October 2, 1990 1
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ATTACHMENT TO LICENSE AMENDMENT NO. 63' I
TO FACILITY OPERATING LICENSE NO. NPF.38 j
DOCKET NO. 50-382 Replace the following pages of the Appendix A Technical Specifications i
with the attached pages. The revised pages are identified by Amendment number and contain vertical _ lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
Remove Insert 6 6-1 6-2*
6-2 6-2a 6-2a 6-5*
6-5 6-6 6-6 6-7 7 6-8 6-8 6-9 6-9 6-10 6-10 6-11*
6-11' 6-12 6-12 6-13 6-13 6-14 6-14 6-15 6-15 6-16*
6-16 l
- 0verleaf page provided for convienece I
1
l ADMfNISTRATIVE CONTROLS t
6.1 Resp 0NSIBILITY 6.1.1 The General Manager Plant Operations shall be responsible for overall l
unit operation and shall delegate in writing the succession to this responsibil-ity during his absence.
6.1.2 The Shift Supervisor, or during his absence from the control room, a designated individual shall be responsible for the control _ room command func-l tion.
A management directive to this effect, signed by the Vice President Operations, shall be reissued to all station personnel on an annual basis.
l 6.2 ORGANI2ATION q
6.2.1 0FFSITE AND ONSITE ORGANIZATIONS Onsite and offsite organizations shall be established for unit operation and 1
corporate management, respectively.
The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
a.
Lines of authority responsibility, and communication shall be established and defined from the highest management levels through intermediate levels to and including all operr. ting organization positions.
These relationships shall be do'.umented and updated, as appropriate, in the form of organization charts, functional descrip-tions of departmental responsibilities.ind relationships, and job descriptions for key personnel positirns, or in equivalent forms of documentation.
These requirements shall be documented in the FSAR.
b.
The Vice President Operations shall have corporate responsibility l
for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintain-1 ing, and providing technical support to the plant to ensure nuclear safety.
c.
The General Manager Plant Operations shall be responsible for overall l
unit safe operation and shall have control over those onsite activ-ities necessary for safe operation and maintenance of the plant, d.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
6.2.2 UNIT STAFF a.
Each on-duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1; WATERFORD - UNIT 3 6-1 Amendment No. 28,41,63
i-ADP.INISTRATIVE CONTROLS UNIT STAFF (Continued) b.
At least one licensed Operator shall be in' the control room'when fuel is in the_ reactor.
In addition, while the reactor is in MODE i
1, 2, 3, or 4, at least one licensed Senior Operator shall beLin the-control room.
s' A Health Physics Technician
- shall be on site when fuel is in the.
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c.
reactor; 4
d.
All CORE ALTERATIONS shall be observed'and directly superiised by.
either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation.
Administrative procedures shall be developed and: implemented.to e.
limit the working hours operating staff who are:,of individuals'of-the-nuclear power plant' responsible for manipulating plant controls-or for adjusting on-line systems and equipment affecting plant safety-which would have an immediate impact on public' health and safety.
Adequate shift coverage shall be-maintained without routinetheavy1
[
use of overtime. The objective shall be to have~ operating personnel.
work a normal 8-hour day, 40-hour week while the plant is-operating..
However, in the event that unforeseen problems require substantial L
6 amounts of overtime to be used, the following guidelines shall be followed:
1.
An individual shall not'be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding' shift turnover time.
2.
An individual shall not be permitted to work nore than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24_ hours in any'48-hour-
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period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7-day period, all'exclud-ing shift turnover time.
i 3.
A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> shall be-allowed between work-periods, including shift turnover time.
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- This requirement tolerates Health Physics Technician unexpected absences'for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, provided management < takes immediate action to fill the required Health Physics Technician position.
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WATERFORD - UNIT 3 6-2 Amendment No. 28,'#2, 58, 61 i
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L' ADNINIST'RATIVE CONTROLS-UNIT STAFF (Continued)-
4.
Except during extended shutdown periods, the use of overtime shall be considered on an individual basis and not for the-entire. staff on a shift.
Any deviation from the above-guidelines'_shall.be authorized by the-General Manager Plant Operations, the Manager Technical Services._the-Manager Operations and Maintenance, the Operations Superintendent or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.. Con-trols shall be-included in the procedures such that individual over-time will be reviewed monthly by the General Manager Plant Operations-l or his designee to assure that excessive hours have not been assigned,-
Routine deviation from the'above guidelines is not authorized.'.
f.
The Operations Superintendent shall hold a senior reactor operator-
- license, WATERFORD - UNIT 3 6-2a Amendment No. 28,#1,50,63
c TABLE 6.2-l' MINIMUM SHIFT CREW COMPOSITION:
POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL-PQSITIO
/-
MODE 1, 2,-3, OR 4-MODE 5 OR 6-SS 1"
SRO-1-
la R0 None.
2 A0 1
2-STA li 18
-Nonel l
Shift Supervisor with a Senior Operator! License SRO Individual with a Senior Operator License RO Individual with an Operator' License
'A0 Auxiliary Operator STA Shift Technical Advisor-than the minimum requirements of Table 6.2-1 for a pe crew members provided imediate action is taken to resto does not permit any shift crew position to be unmanne to an oncoming shift crewman being late or absent..
During any absence-of _the Shift Supervisor from the contro1' room while unit is in MODE 1, 2, 3 or 4.. an individual Advisor) with a valie Senior Operator license (other than the Shift Technical the control room command function.,During any absence of the Shift Sup shall:be designated to assume.
from the control room while the unit is'in MODE 5 or 6. an in valid Senior Operator or Operator license shall be designated to assume control room command function.
"An individual with SRO/STA qualifications can satisfy the SS/STA or SR0/ST position requirements simultaneously.
WATERFORD - UNIT 3 65 AMENDMENT NO. I y
ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)
FUNCTION 6.2.3.1 The ISEG shall function to examine unit operating characteristics.
NRC issuances, industry advisories, Licensee Event Reports, and other sources of unit design and operating experience information, including units of similar design, which may indicate areas for improving unit safety.
The ISEG shall make detailed recommendations for revised procedures, equipment modifications, maintenance activities, operations activities, or other means of improving unit safety to the Director Operations Support and Assessment.
I COMPOSITION 6.2.3.2 The ISEG shall be. composed of at least five, dedicated, full-time engineers located on site.
or related science and at least 2 years professional level experience in hisE field, at least 1 year of which experience shall be in the nuclear field.
_ RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of unit activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
AUTHORITY 6.2.3.4 The ISEG is an onsite independent technical review group that reports to the Director Operations Support and Assessment.
The ISEG shall have the authority necessary to perform the functions and responsibilities as delineated l
above.
RECORDS' 6.2.3.5 Records of activities performed by the ISEG shall be prepared, main-tained, and forwarded each calendar month to the Director Operations Support and Assessment.
6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to the Shift Supervisor in the areas of thermal hydraulics, reactor engineer-ing, and plant analysis with regard to the safe operation of the unit.
The STA shall meet the requirements of either Option 1 or 2 es shown below:
Option 1 - Combined SR0/STA Position.
a.
This option is-satisfied by assigning an individual with the following qualifications to each operating shift crew as one of the SRO's required by 10 CFR 50.54(m) (2) (i):
- Not responsible for sige off function.
WATERFORD - UNIT 3 6-6 AMENDMENT NO.- W,63 1
ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each.' ember of the unit staff shall meet or exceed the minimum qualificatio % of ANSI /ANS 3.1-1978 except that:
a.
The Radiation Protection Superintendent shall meet or exceed the minimum qualifications of Regulatory Guide 1.8, September 1975.
b.
Personnel in the Health Physics, Chemistry and Radwaste Departments shall meet or exceed the minimum qualifications of ANSI N18.1-1971.
c.
The licensed Operators and Senior Operators shall also meet or exceed the minimum qualifications of 10 CFR Part $5.
d.
Personnel in the Nuclear Quality Assurance Department, and other staff personnel who perform insnection, examination, and testing functions, shall meet or excet v.1e minimum qualifications of Regulatory Guide 1.58, Rev.1, September 1980.
(Endorses ANSI N45.2.6-1978).
6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Training Manager-Nuclear and shall 1
meet or exceed the requirements and recommendations of Section 5.2 of ANSI 3.1-1978 and 10 CFR Part 55.
6.5 REVIEW AND AUDIT 6.5.1 PLANT OPERATIONS REVIEW COMMITTEE (PORC)
FUNCTION 6.5.1.1 The PORC shall function to advise the General Manager Plant Operations l
on all m,atters related to nuclear safety.
COMPOSITION 6.5.1.2 The PORC shall be composed of the following members:
Manager Technical Services Manager Operations and Maintenance Plant Engineering Superintendent Maintenance Superintendent Operations Superintendent Radiation Protection Superintendent Management Knowledgeable in Quality Assurance / Control Either the Manager Technical Services or the Manager Operations and Mainte-nance will be Chairman and the Plant Engineering Superintendent will be Vice Chairman.
I WATERFORD - UNIT 3 6-7 Amendmen+ No. Z8, A3 6f, 63
ADMINISTRATIVE CONTROLS i
l ALTERNATES i
i
- 6. 5.1. 3 In the absence of the PORC Chairman and Vice Chairman, the General 1
Manager Plant Operations will appoint a temporary Chairman.
All other alter-t nate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in PORC activities at any one time.
l MEETING FREQUENCY i
6.5.1.4 The.PORC shall meet at least once per calendar month and as convened j
by the PORC Chairman or his designated alternate.
QUORUM j
- 6. 5.1. 5 The quorum of the PORC necessary for the performance of the PORC responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and three members, including alternates.
RESPONSIBILITIES 5
- 6. 5.1. 6 The PORC shall be responsible for the below listed activities.
The PORC may delegate the performance of reviews but will maintain cognizance over i
'the responsibility for them.
Review of (1) all procedures required by Specification 6.8 and a.
changes thereto, (2) all programs required by Specification 6.8 and changes thereto, and (3) any other proposed procedures or changes thereto as determined by the General Manager Plant Operations to l
l affect nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear safety.
Review of all proposed changes to Appendix "A" Technical c.
Specifications.
d.
Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety.
Review of investigations of all violations of the Technical Specifi-e.
cations including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the i
General Manager Plant Operations and to the Safety Review Committee.
l f.
Review of all REPORTABLE EVENTS.
WATERFORD - UNIT 3 6-8 AMENDMENT NO. 3W,.63
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i ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued) g.
Review of unit operations to detect potential hazards to nuclear safety.
h.
Performance of special reviews, investigations, or analyses and i
reports thereon as requested by the General Manager Plant Operations l
i or the Safety Review Committee.
i.
Review of the Security Plan and implementing procedures and submittal of recommended changes to the Safety Review Committee.
t j.
Review of the Emergency Plan and implementing procedures and submittal of recommended changes to the Safety Review Committee.
k.
Review and documentation of judgement concerning prolonged operation in bypast, channel trip, and/or repair of defective protection channels of process variables placed in bypass since the last PORC
- meeting, j
1.
Review of proposed modifications to the CPC addressable constants based on information obtained through the Plant Computer-CPC data link.
l m.
Review of any accidental, unplanned or uncontrolled radioactive l
release including reports covering evaluation, recommendations and l
disposition of the corrective action to prevent recurrence and the l
forwarding of these reports to the Vice President Operations and to l
l the Safety Review Committee.
n.
Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL, and major changes to radwaste treatment I
systems.
o.
Review of the Fire Protection Program and implementing procedures and-I submittal of recommended changes to the Safety Review Committee.
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AUTHORITY 6.5.1.7 The PORC shall a.
Recommend in writing to the General Manager Plant Operations, prior.
l to implementation except as provided in Specification 6.8.3, approval or disapproval of items considered under Specification 6.5.1.6a.
through d. and 1.
b.
Render determinations in writing, prior to implementation except as provided in Specification 6.8.3, with regard to whether or not each item considered under Specification 6.5.1.6a. through e, constitutes an unreviewed safety question.
c.
Provide written notification within 24 hou.rs to the Vice President l
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Operations and the Safety Review Committee of disagreements between l
the PORC and the General Manager Plant Operations; however, the General Manager Plant Operations shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.
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WATERFORD - UNIT 3 6-9 AMENDMENT NO.18. W, 63 e
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.I ADMINISTRATIVE CONTROLS
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j RECORDS
a minimum, document the results of all PORC activities ps;femed under the responsibility and authority provisions of these technical speclii:=tions.
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Copies shall be provided to the Vice President Operations and the Safety Review l
l Committee.
i 6.5.2 SAFETY REVIEW COMMITTEE (SRC)
FUNCTION 6.5.2.1 The SRC shall function to provide independent review and audit of designated activities in the areas of:
a.
Nuclear power plant operations, b.
Nuclear engineering, c.
Chemistry and radiochemistry, d.
Metallurgy, i
e.
Instrumentation and control, l
f.
Radiological safety, g.
Mechanical and electrical engineering and h.
Quality assurance practices.
COMPOSITION 6.5.2.2 The SRC shall be composed of at least five members, including the Chairman.
Members of the SRC may be from within the LP&L organization or from organizations external to LP&L.
1The qualifications of members selected for the SRC shall be in accordance with Section 4.7 of ANSI /ANS 3.1-1978.
ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the SRC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in SRC activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the SRC Chairsan to provide expert advice to the SRC.
WATERFORD - UNIT 3 6-10 AMENDMENT NO. 18, 63 t
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ADM]N1$TRAT]VE CONTROLS MEETINS FRE0VENCY 6.5.2.5 The SRC shall meet at least once per calendar quarter during the
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initial year of unit operatien following fuel loading and at least once per 6 months thereafter.
i QUORUM 6.5.2.6 The quorum of the SRC necessary for the performance of the review and audit function of these technical specifications shall consist of a minimum of five members or of not less than a majority of the composition of members in Specification 6.5.2.2, whichever is greater.
No more than a minority of the members shall h6ve line responsibility for operation of the plant.
REVIEW 6.5.2.7 The SRC shall be responsible for the review of:
The safety evaluations for (1) changes to procedures, equip' ment, or a.
10 CFR 50.59, to verify that such actions did not constitutesyst an unreviewed safety question; b.
Proposed changes to procedures, equipment, or systems which involve an unreviewed safety question as defined in 10 CFR 50.59; Proposed tests or experiments which involve an unreviewed safety c.
question as defined in 10 CFR 50.59; i
License; Proposed changes to Technical Specifications or this Operating d.-
Violations of codes, regulations, orders, Technical Specifications, e.
license requirements, or of internal procedures or instructions having nuclear safety significance; f.
Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety; 9
All REPORTABLE EVENTS; h.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety; and i.
Reports and meeting minutes of the PORC.
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WATERFORD - UNIT 3 6-11 i
- i ADMINISTRATIVE CON 1ROLS
'i i
AUDITS 6.5.2.8 Audits of unit activities shall be. performed under the cognirance of the SRC. These audits shall encompass:
i The conformance of unit operation to provisions contained within the a.
Technical Specifications and applicable license conditions at least once per 12 months.
b.
The performance, training, and qualifications of the entire unit staff at least once per 12 months.
l The results of actions taken to correct deficiencies occurring in c.
unit equipment, structures, systems, or method of operation that
'i affect nuclear safety at least once per 6 months.
d.
The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50, at least once per 24 months, Any other area of unit operation considered appropriate by the SRC e.
or the Vice President Operations.
l f.
The fire protection programmatic controls including the implementing i
procedures at last once per 24 months by qualified licensee QA l
personnel.
g.
The fire protection equipment and program implementation at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer or an outside independent fire protection consultant.
An outside independent fire protection consultant'shall be used at least every third year, h.
The Primary Coolant Sources Outside Containment Program at least once per 24 months.
i.
The In-Plant Radiation Monitoring Program at least once per 24-months.
j.
The Secondary Water Chemistry Program at least once per 24 months.
i k.
The Post-Accident Sampling Program at least once per 24 months.-
4 1.
The Basemat Monitoring Program at least once per 24 months.
The radiological environmental monitoring program and the results m.
thereof at least once per 12 months.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at ~
n.
least once per 24 months.
The PROCESS CONTROL PROGRAM and implementing procedures for proces-o.
sing and packaging of radioactive wastes at least once per 24 months.
l WATERFORD - UNIT 3 6-12 AMENDHENT NO. 18, 63
ADMINISTRATIVE CONTROLS l
AUDITS (Continued) p.
The performance of activities required by the Quality Assurance Program to meet the provisions of Regulatory Guide 1.21. Revision 1, June 1974 and Regulatory Guide 4.1, Revision 1, April 1975 at least once per 12 months.
AUTHORITY 6.5.2.9 The SRC shall report to and advise the Vice President Operations on l
those creas of responsibility specified in Specifications 6.5.2.7 and 6.5.2.8.
_ RECORDS t
6.5.2.10 Records of SRC activities shall be prepared, approved, and I
distributed as indicated below:
a.
Minutes of each SRC meeting shall be prepared, approved, and forwarded to the Vice President Operations within 14 days following each meeting.
l b.
Reports of reviews' encompassed by Specification 6.5.2.7 shall be prepared, approved, and forwarded to the Vice President Operations l
within 14 days following completion of the review, c.
Audit reports encompassed by Specification 6.5.2.8 shall be forwarded to the Vice President Operations and to the management positions l
r risponsible for the areas audited within 30 days after completion of tie audit by the auditing organization.
6.6 REPORT 4.BLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.
ihe Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the PORC and the results of this review shall be submitted to the SRC and the Vice President c
Operations.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the eve.'t a Safety Limit is
. violated.
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WATERFORD - UNIT 3 6-13 AMENDMENT NO. N, 63
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j ADMINISTRATIVE CONTROLS I
SAFETY LIMIT VIOLATION (Continued)
I The NRC Operations Center shall be notified by telephone as soon as a.
possible and in all cases within I hour.
The Vice President Opera-tions and the SRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
I b.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the PORC.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation i
upon facility components, systems, or structures, and (3) corrective action taken to prevent recurrence.
c.
Th'e Safety Limit Violation Report shall be submitted to the Commission, I
the SRC and the Vice President Operations within 14 days of the j
viciation.
i d.
Critical operation of the unit shall not be resumed until authorized by the Commission.
)
6.8 PROCEDURES AND PROGRAMS l
6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978 and those required for imple-f a.
menting the requirements of NUREG-0737.
b.
Refueling operations, Surveillance and test activities of safety-related equipment.
c.
d.
Security Plan implementation, e.
Emergency Plan implementation.
i f.
Fire Protection Program implementation.
I g.
Modification of Core Protection Calculator (CPC) Addressable Constants, including independent verification of modified constants.
NOTES:
(1) Modification to the CPC addressable constants based on information obtained through the Plant Computer - CPC data link shall not be made without prior approval of the PORC.
(2) Modifications to the CPC software (including algorithm changes and changes in fuel cycle specific data) shall be performed in accordance with the most recent version of CEN-39(A)-P, "CPC Protection Algorithm Software Change Procedure," that has been determined to be applicable to the facility.
Additions or deletions to CPC Addressable Constants or changes to Addres-sable Constant software limits values shall not be implemented without prior NRC approval, i
h.
4dministrative procedures implementing the overtime guidelines of Specification 6.2.2e., including provisions for documentation of deviations.
i.
PROCESS CONTROL PROGRAM implementation.
a WATERFORD - UNIT 3 6-14 Amendment No. 5, 6f, 63 -
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i ADMINISTRATIVE CONTROLS s
PROCEDURES AND PROGRAMS (Continued) j.
OFFSITE DOSE CALCULATION MANUAL implementation.
k.
Quality Assurance Program for effluent and environmental monitoring, i
using the guidance in Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4.1, Revision 1 April 1975.
6.8.2 Each procedure of Specification 6.8.1, and changes thereto, shall be reviewed as specified in Specification 6.5.1.6 and shall be approved by the General Manager Plant Operations prior to implementation and reviewed periodi-cally as set forth in administrative procedures.
l 1
6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made provided:
a.
The intent of the original procedure is not altered; b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Operator license on the unit affected; c.
The change is documented, revienced by the PORC and approved by the Gen;;ral Manager Plant Operations within 14 days of implementation.
l 6.8.4 The following programs shall be established, implemented, and i
maintained:
i a.
Primary Coolant Sources Outside Containment l
r A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a l
serious transient or accident to as low as practical levels.
The systems include the containment spray, safety injection, hydrogen analyzer, and the post-accider.t sampling system.
The program shall l
include the following:
1.
Preventive maintenance and periodic visual inspection requirements, and 2.
Integrated leak test requirements for each system at refueling I
cycle intervals or less, b.
g-PlantRadiationMonitorina A program which will ensure the capability to accurately; determine the airborne iodine concentration in vital areas under accident conditions.
This program shall include the following:
i
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WATERFORD - UNIT 3
.6-15 Amendment No.63 t
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i ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 1.
Training of personnel, J
2.
Procedures for monitoring, and 3.
Provisions for maintenance of sampling and analysis equipment.
I c.
Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit l
steam generator tube degradation.
This program shall include:
1.
Identification of a sampling schedule for the critical i
variables and control points for these variables, 1
2.
Identification of the procedures used to measure the values of the critical variables, 3.
Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in-leakage, 4.
Procedures for the recording and management of data, 5.
Procedures defining corrective actions for all off-controi point chemistry conditions, and 6.
A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and. timing of administrative events required to initiate' corrective action.
d.
Post-accident Samplino A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident J
conditions.
The program shall include the following:
j
' 1.
Training of personnel, 2.
Procedures for sampling and analysis, and 3.
Provisions for maintenance of sampling and analysis equipment.
{
e.
Basemat Monitorino A program for monitoring of the Nuclear Plant Island Structure (NPIS)
Common Foundation Basemat to ensure the continued integrity of the Basemat.
The program shall include:
1.
settlement of the basemat 2.
changes in ground water chemistry that could effect corrosion of reinforcing steel 3.
seasonal variation in ground water levels 4.
mapping of significant cracking in the basemat and adjacent walls.
WATERFORD - UNIT 3 6 16
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